This report covers the following titles: (1) Fertility and litter size of normally ovulated and artificially ovulated mice; (2) Further studies on sterility produced in male mice by deuterium oxide; (3) Planarian disaggregation; (4) Uptake of organic compounds by planarians. II; (5) Effects of environmental complexity and training on acetylcholinesterase and cholinesterase activity in rat brain; (6) Effects of environmental complexity and training on brain chemistry and anatomy among mature rats; (7) Improvements in paper chromatographic techniques for labeled cell extracts; (8) measurement and adjustment of pH in small volumes of solutions; (9) Carbon-14 and Nitrogen-15 tracer studies of amino acid synthesis during photosynthesis by Chlorella Pyrenoidosa; (10) Photosynthesis of {sup 14}C-labeled protein from {sup 14}CO{sub 2} by Chlorella; (11) Further studies on carboxydismutase; (12) Electron microscopy of chlorophyll a crystals; (13) The possible role of chromanyl phosphates in oxidative and photosynthetic phosphorylation; (14) Oxidation-reductions of some coenzymes; (15) Preparation of some [{sup 14}C] labeled substances: glucose-6-phosphate, fructose-6-phosphate, 6-phosphogluconic acid, pyruvic acid, and succinic acid; (16) attempt to synthesize high molecular weight polynucleotides using Schramm's purely chemical method; and (17) Optical properties of some dye-polyanion complexes.

The ground-state wave function and energy of a finite system of interacting fermions are expanded in terms of multiple-particle excitations on an uncorrelated zero-order state. The resulting set of coupled equations constitutes a systematic variational generalization of Hartree-Fock theory. Comparison is made with many-body perturbation theory and it is shown that to any order the theory incorporates an infinite number of perturbation theory terms. Solutions of the equations for ground-state atomic systems are discussed and related to previous work using many-body perturbation theory. It is shown that the sums of perturbation terms necessary for convergence are automatically included in the equations for two-particle excitations. Application of the equations to open-shell atoms is described.

This document details activities of the irradiation processing department during the month of June, 1963. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; and Financial Operation.

This report, from the Chemical Processing Department at HAPO for June 1963, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations, facilities engineering; research; and employee relations; weapons manufacturing operation; and power and crafts operation.

This purpose of this test is to acquire data to support further studies aimed at determining whether a normal column of I&E enriched fuel elements or a normal column of natural fuel elements can be flushed from a process tube with the crossheader valved down to shutdown position if the front riser pressure is raised to normal operation pressure.

This is the monthly report for the Hanford Laboratories Operation, June 1963. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

The ``machined parts`` casks are shipped to Hanford by Savannah River for loading with irradiated lithium alloy slugs and returned for processing. The casks have been in service for about 10 years and have shielding material more than what is required by regulations for radiation attenuation. Evaluation shows that rupture of the shell is probable for edge or corner drop, with considerable displacement of shielding. The cask would fail in a 2-hour fire of 2000 F with loss of shielding and probable dispersal of the product. Bolts securing cover to cask are inadequate in event of accident.

The nuclear heat generation rate in the first capsule irradiated was higher by a factor of two than was calculated. The original capsule was irradiated in a dry bore with cooling water in the annulus only. The new capsule will be irradiated in a water-cooled bore facility with additional cooling coils around the lithium containing tube. This will keep the inner capsule temperature below 150 C during the initial tritium buildup period prior to outgassing. This Supplement authorizes the irradiation of an additional capsule and the removal of the present facility and installation of a single tube general purpose facility. All remaining provisions of the original development test are in force except for minor exceptions due to the water flow in the bore which have been changed in the following writeup.

A study on low flow in tubes indicates that the below normal coolant flow is due to an abnormality in the rear hardware. It is suggested that reaming the rear Parker fittings on the tubes and subsequently inspecting the venturi gauges is an good solution.

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An important parameter which is required in the study of short-term reactor transients is the prompt neutron lifetime. This document presents calculated values for the prompt neutron lifetime in the Hanford IPD lattices under a variety of conditions. The calculated values for the prompt neutron lifetimes in the various Hanford IPD lattices are shown. None of the values shown include any contribution from the neutron slowing down time. Two different values (1{sub o1} and 1{sub o2}) are presented for each lattice spacing and condition studied. This arises from an uncertainty about the correct definition of the thermal neutron lifetime. Generally speaking, it is conservative, from a hazards analysis standpoint, to use the shorter values. This has been done in all of the kinetics studies concerning the production reactors at Hanford during the last several years. A precise definition and more complete discussion of the values presented are given later in this report.

Test K-4-14 described in this report, was the second ``full charge`` test to be irradiated in KER-4 following loop modification under Project CGI-839. It provided an opportunity to accumulate additional data on the behavior of N Reactor fuel elements at conditions equivalent to or more severe than those anticipated in N Reactor during Phase I, equilibrium operation. Objectives and test results are provided.

A unique mechanical drive system with associated transistorized circuitry has been developed to allow digital recording on magnetic tape at carrying data flow rates. The present system records on command at rates up to 40 characters per second with a packing density of 200 characters per inch. The output is on half-inch magnetic tape in a format compatible with conventional playback equipment.

The effective delayed neutron characteristics of a reactor are dependent on the relative fission rates in the various fissionable isotopes present. The delayed characteristics of the production reactors are presented as a function of exposure.

Purpose of this chapter is to provide an overview of reactor construction and an understanding of important design considerations: how it is built, why it was built that way, what it is supposed to do, what the nuclear safety considerations are, and what one needs to know about its design/construction to properly operate it.

The growing concern of government agencies for safe shipment of radioactive materials, both in this country and in Europe, has resulted in a number of proposed regulations governing every phase of shipment including the design of the cask or container, There have been requests during the last year for increased shipments of irradiated bismuth from Hanford. This radioactive material has been shipped in the B-cask to the off-site processing plant for several years. These two factors, proposed regulations and increased demand for the product, have created a need for an engineering evaluation of the cask currently being used. While it is evident on casual inspection that the B-cask design would not meet certain requirements of the proposed regulations, it is necessary that a detailed study of the design be made to determine if modifications to the cask are practical for continued use under new regulations and whether additional casks should be of a new design as required by increased shipments of the product. The purpose of this design evaluation study is to: (a) Evaluate the integrity of the B-cask design in accordance with criteria published in document HW-76476, which is based primarily upon proposed regulations of the Atomic Energy Commission …

Irradiation of process tubes containing appropriate parent materials has been proposed by Manufacturing as a method for obtaining new products from the Hanford Reactors. The process tubes would be removed at appropriate intervals and shipped to separations plants for recovery of the products. The tube residence in the reactor could be determined by the optimum irradiation period for isotope production rather than by the period required to corrode tubes of current design to the minimum permissible wall thickness at replacement. This paper, presents an analysis to determine the benefits from red reducing the initial wall thickness of the process tubes below the current 65 mils when the desired residence for isotope production is shorter than the residence based on maximum permissible internal corrosion for tubes of current design.

If for an unspecified reason it becomes necessary to shut down all eight production reactors for an extended period exceeding normal outage times, the following procedures are recommended. These procedures have been devised to render the maximum safe situation short of complete core discharge and to enable as efficient a reactor startup as possible following the outage. Specific topics include: general safety, startup efficiency, detailed shutdown procedure of reactor and water plant, and startup procedure. (GHH)

Irradiation of Np-237 in Hanford reactors and recovery of the Pu-238 product in a close-coupled separations plant is currently of interest. Such a concept has the potential of increasing in Pu-238 production rates. The results of initial calculations on the subject are presented herein to aid further study and evaluation. Much of the information is presented in terms of the aqueous target system proposed in earlier work (i.e., irradiation and processing of an aqueous neptunium solution). However, most of the information can be converted for evaluation of a solid target system.

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Reactor Fuel Elements--temperature peaking in SNAP due to surrounding rods; systems for nuclear auxiliary power (SNAP)--reactor fuel temperataure peaking due to surrounding fuel rods; temeprature--calculations of peaking of, in SNAP fuel due to sourround fuel rods.

Work reported includes: Chemical-Metallurgical Processing; Fuel Cycle Applications of Volatility and Fluidization Techniques; Calorimetry; Reactor Safety; Energy Conversion; and Determination of Nuclear Constants.

A description is presented of a preliminary bending analysis of three module configurations designed for the 19-hole Kiwi-B4-type fuel element.

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